ML20154P624
| ML20154P624 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/17/1988 |
| From: | Conlon T, Merriweather N, Paulk C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20154P622 | List: |
| References | |
| 50-348-88-16, 50-364-88-16, NUDOCS 8806060014 | |
| Download: ML20154P624 (6) | |
See also: IR 05000348/1988016
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UNITED STATES
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RUCLEAR REGULATORY COMMISSION
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REGION il
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101 MARIETTA STRE ET, N.W.
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ATLANTA, GEORGI A 30323
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Report Nos.: 50-348/88-16 and 50-364/88-16
Licensee: Alabama Power Company
600 North 18th Street
Birmingham, AL 35291-0400
Docket Nos.:
50-348 and 50-364
Facility Name:
Farley 1 and 2
Inspection Conduc ed: April 19-21,1983
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Inspectors:
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N. /Nerriwea ther
Date Signed
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Accompanying Personnel:
T. E. Conlon
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Approved by:.T.'E. Conlon, Section Chief
Date Signed
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Plant Systems Section
Division of Reactor Safety
SUMMARY
Scope:
This special, announced inspection was in the area of Environmental
Qualification (EQ) of Electrical Equipment and involved followup on Unresolved
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Items 50-348, 364/87-30-04, 10 and 12 and Violation. 50-348, 364/87-30-15.
Results:
No violations or deviations were identified.
8806060014 880519
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
- S. Fulmer, Supervisor, Safety Audit Engineering Review
- J. Garlington, Manager, Engineering and. Licensing
- D. H. Jones, Manager, Nuclear Engineering
- W. B. Shipman, Assistant Plant Manager - Support
- J. D. Woodard, General Manager, FNP
Other Organization
- J. Love, Assistant Project Engineer, Bechtel Engineering
- J. E. Sundergil, EQ Group Supervisor, Bechtel Engineering
NRC Resident Inspectors
W. Bradford, Senior Resident Inspector
- W. Miller, Resident Inspector
- Attended exit interview
- Attended entrance meeting on April 19, 1988
2.
Exit Interview
The inspection scope and findings were summarized on April 21, 1988, with
those persons indicated in paragraph 1 above.
The inspectors described
No
the areas inspected and discussed in detail the inspection findings.
However, the
dissenting comments were received from the licensee.
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licensee did make certain commitments which are discussed in Paragraphs _3.a
and 3.d.
The licensee did identify some material as proprietary during this
inspection, but this material is not included in this inspection report.
3.
Licensee Action on Previous Enforcement Matters
a.
(0 pen) Violation 50-348,364/87-30-15, Raychem/ Chico-A Seals
A previous inspection had identified the licensee's failure to
establish qualification for the Raychem/ Chico-A seals for moisture
barriers on Namco Limit Switches both inside containment and in the
Main Steam Room (MSR).
Subsequent to that inspection, the licensee
provided additional information which indicated that the seal design
used in the MSR was different from the one used inside containment in
that no Chico-A sealing compound was used.
However, neither design
was shown to be qualified to the 00R Guidelines or NUREG OS88, CAT
II criteria.
Additional test data was provided which indicates that
the design with the Raychem boot used in the MSR was tested for
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submergence at' 212 F for four hours and a cooldown and soak of 20
hours at a pressure head of approximately ten feet (5 psig).-
This
test data -was not adequate to demonstrate qualifications for Main
Steam Line Break accident in the MSR with peak temperatures of
approximately 326
F.
In a letter dated April 4,1988, - APC0 comitted to replace all
Raychem/ Chico-A seals on Namco limit switches inside Unit.1
containment prior to restart from the current _ refueling outage.
Additionally, APC0 committed to' replace these same seals in Unit 2
During
containment during the next ou: age of sufficient. duration.
this inspection APC0 committed to install an acceptable cable
entrance configuration for the Namco Limit Switches in the MSR's on
Furthermore, APC0
both units during the next refueling outage.
committed to provide a justification for continued operations for-
Units 1 and 2 to the NRC for evaluation and acceptance prior to
Unit I restart.
The previously identified violation is still open and being e. valuated
for escalated enforcement.
(Closed) Unresolved Item 50-348, 364/87-30-04, Failure to Train
b.
Personnel Involved in EQ Activities in the Requirements of the EQ
Program.
Actions taken by the licensee to resolve this issue were discussed
during the enforcerrent conferent e held in the NRC Region II office on
1988.
In this meeting, the licensee stated that the
March 15,
following imediate corrective actions had been implemented:
Plant training plan has been revised to require training for
Technical Staff and Managers
The FNP QC engineer and his staff, and the Plant Modifications
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group have been trained on EQ
Appropriate General Office Staff personnel have also been
trained on EQ
Licensed operator will be trained as part of upcoming requali-
fication training
A review of training attendance sheets confirmed the implementation
of the corrective action.
Based on the above, this item is
considered closed.
c.
(Closed) Unresolved Item 50-348,364/87-30-10, Raychem Stilan Cable
This cable was not considered qualified during the inspection because
the IR values given in the report have no meaning.
Subsequent to that
inspection the licensee provided information on their commitments to
In a letter dated
the commission to meet Regulatory -Guide 1.97.
June 12, 1984, from NRC,
S.
Varga to Mr. R. P. Mcdonald, the
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confirmatory order based on certain APC0
issued a
Commission
The order required APC0 to implement RG 1.97 require-
commitments.
ments on Unit 1 by March 1988, and on Unit 2 by October 1987.
The licensee stated that the Stilan Cable was added to the EQ Master
The Stilan cable has been replaced as part of the-
list by error.
Reg. Guide 1.97 upgrade for Unit 2 and will be. replaced on Unit i
during the eighth refueling outage.
This item is, therefore, considered closed.
(0 pen) Unresolved Item 50-348, 364/87-30-12, Certain S0Vs may not be
d.
Qualified Due to a Lack of Cable Entrance Seals.
A major environmental qualification concern involves the absence of
cable entrance seals on Automatic Switch Company (ASCO) Solenoid
valves that are required to be energized and/or cycled during a
design basis accident.
The valves effected by this concern are
A detail description
located both inside containment and the MSR.
of these valves is included in Appendix A to'this report.
The NRC inspe . ors reviewed ASCO test reports (AQS 21678/TR Rev. A
and AQR-67368/Rev.1), FRC Test Report (NUREG 3424) and GPC Hatch
The
Test Report on LOCA/MSLB Testing of ASCO solenoid valves.
inspectors concluded that the ASCO reports by themselves did not
The
adequately address the anomalies due to moisture intrusion.
Franklin report was inconclusive as to whether ASCO housings were
seal tight under LOCA conditions because they did not use a known
qualified seal configuration.
The only test report that obtained
However, there
good results appeared to be the GPC Hatch Report. Based on review of
still remained some questions with this report.
the above, the inspectors concluded that Farley's ASCO configurations
were not qualified because they had not adequately addressed the
anomalies caused by moisture intrusion.
Therefore, to_ resolve this
concern ADC0 proposed the following corrective actions:
develop a JC0 for S0Vs required for long term
(1) APC0 will
This JC0 will consider existing . test data, farley
operation.
configuration and short duration environmental profile for the
APC0 will submit the JC0 to NRC for evaluation and
MSR.
acceptance.
APC0 will modify the existing conduit configuration on both
(2)
units in the MSRs to permit when possible moisture drainage away
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from the solenoid housing.
Those in Unit I will be modified
prior to plant restart,
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(3) APC0 will develop a JCO for.five S0Vs required for long term
The JC0 will be
operations inside Units 1 and 2 containments. formulated to me
prior to restart of Unit I to NRC for evaluation and acceptance.
APC0 will modify the flex conduit on one.PORY S0V, inside Unit I
(4)
This also will
containment, to provide for moisture drainage.
be completed prior to Unit I restart.
The inspectors examined S0V installations in the MSR on Unit 1--and
reviewed photographs of all ten long term S0V containment configura-
tions.
~ The inspectors concluded that these configurations are
somewhat similar to what was tested by ASCO in the above testThis
reports, however, the anomalies were not adequately addr
completion of proposed long term corrective actions.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
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APPENDIX A
LIST OF ASCO SOLEN 010 VALVES WITHOUT CABLE ENTRANCE SEALS
Component
Equipment Function
Location
Comments
N11SV3369AC-A
Main Steam Isolation
Note 1
N11SV3369BC-A
Main Steam Isolation
Note 1
N11SV3369CC-A
Main Steam Isolation
Note 1
N11SV3370AC-B
Main Steam Isolation
Note 1
N11SV3370BC-8
Main Steam Isolation
Note l'
N11SV3370CC-B
Main Steam Isolation
Note 1
N11SV3916A-B
Main Steam Bypass
Note 1
N11SV397L3-8
Main Steam Bypass
Note 1
N12SV3235A-AB
Steam Admission to Turbine
Note 1
Driven Auxiliary Feedwater
(TDAFW)
N12SV3235B-AB
Steam Admission to TDAFW
Note 1
N235V3227AA-A
Note 2
Control
N23SV3227AC-B
Note 2
N23SV3227BA-A
Note 2
N23SV3227BC-8
Note 2
N23SV3226CA-A
Note 2
N23SV3227CC-B
Note 2
N23SV3228AA-AB
TD AFW Flow Control
Note 2
N23SV3228BA-AB
TD AFW Flow Control
Note 2
N23SV3228CA-AB
TD AFW Flow Control
Note 2
831SV0444BA-B
Pressurizer (PZR) P0RV
Note 2
B31SV0444BA-A
PZR PORY
Note 2
831SV0445AA-A
PZR PORV
Note 2
B31SV0445AB-A
PZR PORV
Note 2
P17SV3184-B
Note 3
Note 1:
Energized, does not change state during accident
Note 2:
Changes state periodically during accident
Note 3:
Energized on a Phase B isolation.
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